ML17255A746
| ML17255A746 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/30/1980 |
| From: | BOSTON INSULATED WIRE & CABLE CO. |
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| References | |
| B-915, NUDOCS 8404100411 | |
| Download: ML17255A746 (82) | |
Text
BOSTRAD CABLES FLAME AND RADIATION RESISTANT CABLES FOR NUCLEAR POWER PLANTS REPORT NO. B 915 NOVEMBER 1980 BOSTON INSULATED WIRE & CABLE CO ~
65 Bay Street Boston, Massachusetts 02125
CONTENTS Section Pacae I. INTRODUCTION II.
SUMMARY
III. CABLE CONSTRUCTIONS IV. 40 YEAR LIFE V. THERMAL AND RADIATION EXPOSURE VI ~ NUCLEAR RADIATION-LOCA ENVIRONMENTAL PERFORMANCE 10 VII. FLAME RESISTANCE VERTICAL TRAY FLAME TESTS 19 VIII. LONG TERM WATER ABSORPTION 26
FIGURES N er Pa<ac TYPICAL 2/C AND 7/C CABLES
- 2. ARRHENIUS AGING CURVES
- 3. LONG TERM ARRHENIUS AGING ON CABLES 4 ~ THERMAL AND RADIATION EXPOSURE TEST
- 5. LOCA SIMULATION DATA, NEW CABLE 11-12
- 6. LOCA SIMULATION DATA, AGED CABLE 13-14
- 7. LOCA SIMULATION DATA, AGED CABLE 15-16
- 8. LOCA S IMULATION DATAt AGED CABLE CONTAINING A SPLICE 17
- 9. VERTICAL TRAY FLAME TEST, 2/C CABLE 20 VERTICAL TRAY FLAME TEST, 7/C CABLE 21 VERTICAL TRAY FLAME TEST, AGED CABLE 22
- 12. VERTICAL TRAY FLAME TEST, AGED CABLE 23
- 13. VERTICAL TRAY FLAME TEST, 210,000 BTU 24
- 14. VERTICAL TRAY FLAME TEST g AGED CABLE 21 0 g 0 0 0 B TU 25
- 15. LONG TERM ACCELERATED WATER ABSORPTION, ELECTROENDOSMOS IS 26
- 16. LONG TERM ACCELERATED WATER ABSORPTION'M-60 METHOD 27
BIW This report is proprietary and the subject matter herein is strictly confidential. The report or information Insulated can not be used for any purpose other than in connection with Boston Wire and Cable Company products. All rights hereto are reserved and this report may not be copied or distributed in whole or part without specific approval from the Boston Insulated Wire and Cable Company.
I. INTRODUCTION W Flame and Radiation Resistant Cables BOSTRAD 7E Cables with BIW's ethylene propylene rubber (EPR) insulation and BOSTRAD 7 chlorosulfonated polyethylene (CSPE) jackets have indicated life in excess of 40 years and excellent flame resistance. They are also radiation resistant, exceed LOCA environmental requirements and have excellent moisture resistance, as demonstrated by long term accelerated water absorption tests.
The outstanding performance of these cables is demonstrated by prototype tests in accordance with IEEE-383 on typical cables manufactured by BIW.
II.
SUMMARY
This report describes the qualification of BOSTRAD 7E cable constructions to the requirements encountered in nuclear and fossil fueled power plants.
1 2 Type tests in accordance with IEEE 323-1974 and IEEE 383-1974 have been conducted which demonstrate the suitability of BOSTRAD 7E cables for installation in power plants. These tests include fire, LOCA, thermal endurance, radiation resistance, and water immersion.
IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations.
IEEE Standard for Type Test of Class IE Electric Cables, Field Splices and Connections for Nuclear Power Generating Stations.
III. CABLE CONSTRUCTIONS BOSTRAD 7E cables are manufactured in accordance with BIW Specifying Standards and ICEA Standard S-68-516. Power, control and instrumentation cables are available, featuring the following construction:
Conductors Class B stranded tinned copper, con-forming to ASTM B8 and B33.
Insulation Ethylene propylene rubber, con-forming to ICEA S-68-516.
Insulation Jacket BOSTRAD 7 CSPE, conforming to ICEA S-19-81.
Voltage Rating 1,000 V, 600 V or 300 V Shield (if required) Aluminum/polyester or copper/
polyester tape with stranded tinned copper drain wire, 100% coverage, or tinned copper braid.
Fillers (if required) Flame retardant glass fiber or flame retardant synthetic rubber.
Flame Tapes(if required) Flame retardant binder tapes.
Outer Jacket BOSTRAD 7 CSPE, conforming to ICEA S-19-81.
Figure 1 gives typical constructions of the 2/C and 7/C cables.
These cables have been subjected to the qualification tests described herein.
FIGURE 1 2 CONDUCTOR CABLE Conductors Two 416 AWG 7/.0192" tinned copper Dual Layer Insulation 25 mils ethylene propylene rubber with 15 mils BOSTRAD 7 CSPE jacket Shield Aluminum/polyester tape with 418 AWG 7/.0152" tinned copper drain wire Jacket 45 mils BOSTRAD 7 CSPE TYPICAL 7 CONDUCTOR CABLE Conductors Seven 412 AWG 7/.0305" tinned copper Dual Layer Insulation 30 mils ethylene propylene rubbe with 15 mils BOSTRAD 7 CSPE jacket Outer Jacket 60 mils BOSTRAD 7 CSPE
IV. 40 YEAR LIFE Long term aging tests conducted on cables indicate a life expectancy in excess of 40 years at 90C for BIW's ethylene propylene rubber insulation.
Aging was accelerated using the Arrhenius technique described below.
The aging characteristics of BIW's ethylene propylene rubber and CSPE compounds were found by monitoring the elongation of these compounds after exposure to different temperatures for varying times.
This was done by placing hundreds of samples of each compound in ovens at 121C, 136C, 150C, 180C and 200C, and after prescribed intervals, removing samples from each oven and measuring ultimate elongation.
The results of elongation versus time at each temperature are shown in Figure 2A.
The data in Figure 2A is transformed into a temperature versus time relationship by selecting various conditions of elongation and plotting the locus of time and temperature on semi-logarithmic paper (Figure 2B). It can be seen that for any selected value of elongation, the curves are essentially straight and parallel.
Arrhenius theory in the temperature range investigated is validated by e straight line, i.e. the straight lines demonstrate a constant rate.
reaction in the region. Since a rate of aging has been determined or the cable, then for any defined service condition, a line having the predetermined aging rate (slope) can be constructed through the point representing the service condition, and all points on the line will be equivalent to the defined service condition.
Elongation, however, cannot be related directly to the ability of a cable to function for a given time and temperature. However, cable can withstand dielectric proof testing after aging, its life is if a verified. Therefore, to demonstrate qualified life, BIW ages cable samples to the desired service conditions and, after this aging and bending to 40X cable OD, dielectrically proof .tests the cable.
BOSTRAD 7E cables have been type tested to qualify for a 40 year, 90C service life. This has been done by constructing a line with the slope shown in Figure 2B through the desired 40 year, 90C point, as shown in Figure 3. To simulate this end life, BIW placed cable samples in air ovens at 200C, 180C, 150C, 136C and 121C. These cables were removed from the ovens periodically and subjected to a dielectric proof test of 2200 volts (twice rated voltage + 1000 in accordance.
with IEEE 383-1974, para. 2.3.2.). After successfully withstanding the test, the samples were returned to the oven for continued aging.
IV. 40 YEAR LIFE (Cont. )
BOSTRAD 7E cable samples aged in excess of the 40 year equivalency requirement at 200C, 180C, 150C, 136C and 121C, were bent around a 40X diameter mandrel and withstood the voltage proof test. These type tests demonstrate the capability of the cable to function after being aged to the equivalent of 40 years life at 90C.
DATA ARRHENIUS AGING FIGURE 2A 100 1'5 z
0 0
50 O
5O n n
0 1 000 2 00 3,000 4POO 5, 00 6POO 7, 00 BPOO TIME (HOURS)
FIGURE 28 10 2596 ELONGATION 100% ELONGATION 20096 ELONGATION 10 0
K 3 10 I
6 K
0 10 10 180 150 136 121 110 TEMPERATURE C (1/ K SCALE)
FIGURE 3 1,000.000 LONG TERM AGING 1/C. 2/C. 4 7/C CABLES CONDUCTORS - STRANDED TINNED COPPER INSULATION ETHYLENE PROPYLENE RUBBER WITH BOSTRAD 7 CSPE JACKETS (1) 0 YR, 90C POINT ALUMINUM-POLYESTER TAPE SHIELD WITH STRANDED TINNED COPPER DRAIN WIRE (MULTICONDUCTOR CABLES) 0 YR.
OUTER JACKET- BOSTRAD 7 CSPE (1) CABLES TESTED 100.000 1/C ¹6 AWG 45/25 WALLS 2/C ¹12 AWG 30/15 WALLS 2/C ¹16 AWG 30/15 WALLS 7/C ¹16 AWG 30/15 WALLS LINE FOR 40 YR. LIFE AT 90C SLOPE DERIVED FROM PRIOR 2/C ¹16 AWG 20/15 WALLS AGING TEST DATA.
10.000 0K I.
I z6 6
1.000 CODE:
p B B ~ TEST POINT PASSES 2200 VOLTS B ~ B TEST POINT PASSES 2200 VOLTS AFTER 40X BEND
~D TEST DISCONTINUED 100 TEMPERATURE oC (1/oK SCALE) 10 200 180 150 136 121 100 80
BIW V. THERMAL AND RADIATION EXPOSURE BOSTRAD 7E cables have excellent resistance to combined exposures of heat and radiation.
Bend tests in accordance with IEEE Standard 383-1974, para.
2.3.3., are shown in Figure 4. After a gamma radiation dosage of 200 megarads and thermal conditioning of 60 days at 155C, the cable passed the required 20X bend.
The thermal aging is equivalent to 40 years at 90C as shown by Figure 3.
Additional data concerning thermal and radiation exposure may be found in Section VI, Nuclear Radiation-LOCA Environmental Performance.
The LOCA simulation is regarded as a more severe performance test, and demonstrates the outstanding capability of BOSTRAD 7E to exceed the standard tests by a comfortable margin.
FIGURE 4 THERMAL AND RADIATION EXPOSURE TEST Thermal aging 155C for 60 days (1440 hours) equivalent to 40 years at 90C, followed by 2 x 108 r ads gamma radiation Cable Construction 2/C 416 as in Figure l.
Test Re uirements IEEE 383-1974, para. 2.3.3.
20x Bend -- 2.0 KVAC in water for 5 minutes
~ 'est Results Before Bend Pass 2.2 KVAC dry After 20x Bend Pass 2.2 KVAC in water for 5 minutes
BIW VI. NUCLEAR RADIATION-LOCA ENVIRONMENTAL PERFORMANCE BOSTRAD 7E cables perform through service conditions encountered during both normal and LOCA operation in nuclear power plants, as shown by their passing the LOCA simulation tests of IEEE Standard 323-1974, Appendix A, Figure Al, and para. 2.4.3.1.
The cables were irradiated to the levels indicated in the data at ISOMEDIX, INC., Parsippany, New Jersey by exposure to a Cobalt 60 source. The cables were then subjected to the steam and pressure LOCA simulation in autoclave chambers at the Boston facility of Boston Insulated Wire 6 Cable Company.
Figures 5, 6, 7 and 8 demonstrate the typical performance of BIW
. BOSTRAD 7E cables under LOCA environmental conditions. BIW has successfully performed many LOCA tests on BOSTRAD 7E cables and continues to perform tests to verify BOSTRAD 7E's outstanding performance.
Figure 5 shows an unaged 2/C 416 AWG cable which, after a gamma radiation dose of 200 megarads, was exposed to the IEEE Std. 323-1974 LOCA environmental conditions. The cable successfully performed 367 days and then met all the requirements of the post LOCA simulation test.
Figure 6 presents data for a- 2/C 416 AWG cable which, after I thermal aging of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121C (equivalent to 40 years at 50C) a a gamma radiation dose of 200 megarads, was exposed to the LOCA environmental conditions. The cable successfully withstood these extremes for 367 days and then met all the requirements of the IEEE Std. 383-1974 post LOCA simulation test.
Figure 7 presents data for a 2/C gl6 AWG cable which, after thermal aging to a condition representing 40 years life at 90C (Figure
- 3) and a gamma radiation dose of 200 megarads, was exposed to the LOCA environmental conditions. The cable successfully withstood these extremes for 161 days and then met all the requirements of the IEEE Std. 383-1974 post LOCA Simulation Test.
Figure 8 presents data for a 1/C 012 AWG cable containing a splice which, after heat aging to a condition representing 40 years life at 90C (Figure 3) followed by a gamma radiation dose of 200 megarads, was exposed to the LOCA environmental conditions. The cable successfully withstood these extremes for ill days and then met all the requirements of the IEEE Std. 383-1974 post LOCA Simulation Test.
10
FIGURE 5 LOCA SIMULATION DATA New Cable 8
Cable Construction 2/C 416 as in Figure l.
Test Re uirements Environmental Simulation Cycle per IEEE 323-1974, Appendix A, combined cycle for PWR/BWR Cable sprayed with 0.28 molar H3B03 solution adjusted to pH of 10.5 with NaOH for first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and with mineral-free water thereafter through the first 30 days only.
Test Results IR Pressure Cdr Cdr Time Tymp.
F Psig Steam Megohms per test length 20 ft.
90 0 7.0 x 10 0
End of 3 hrs. 340 115 3.5 x 10 4 hrs. 160 0 1.2 x 10 7 hrs. 340 115 3.7 x 10 10 hrs. 320 85 7.6 x 10 14 hrs. 300 65 1.0 x 10 26 hrs. 250 16 1.3 x 10 2
3 days 250 16 2.4 x 10 6 days 200 0 6.0 x 10 4
10 days 200 6.0 x 10 35 days 200 7.8 x 10 100 days 200 1.1 x 10 (1) 367 days 167 2.2 x 10 (2) 600 volts applied between conductors throughout the test. Current of 1 amp/conductor throughout the test.
Figure 5 (Continued)
Post LOCA Tests (IEEE STD. 383-1974)
(1) The LOCA test was continued at 200F, 0 psig and 100% RH for a total of 100 days. After the 100 day cycle, the cable was subjected to a post LOCA test consisting of 40x, 20x, 10x and 5x mandrel bends. The cable withstood a 5 minute 2200 volt dielectric test after each bend.
(2) The LOCA test was continued again at 167F, 0 psig and 100% RH for a total of 367 days. The cable then passed an additional post LOCA bend test of 40x and 2200 VAC for 5 minutes in water.
40d 350 4F 34 32 F 3 d'F 30d 250 201t 167 F 0 0.1 5 10 50 100 500 1000 5000 10000 1IMS (HOUl$1 12
BIW FIGURE 6 LOCA SIMULATION DATA Cable A ed to E uivalent of 50C for 40 Years Thermal aging at 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121C followed by 2 x 10 8 rads, gamma.
Cable Construction 2/C 416 AWG as in Figure l.
Test Re uirements Environmental Simulation cycle per Appendix A, IEEE Std. 323-1974, combined cycle for PWR/BWR.
Cable sprayed with 0.28 molar =H3B03 solution adjusted to pH of 10.5 with NaOH for first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and with mineral-free water thereafter through the first 30 days only.
Test Results Pressure Cdr Cdr Time Tsmp F
o Steam'R Psig Megohms test per 20 length ft.
125 0 25 x 10 4 End of 3 hrs. 340 105 1.2 x 10 0
2 4 hrs. 160 0 7.3 x 10 7 hrs. 340 105 1.6 x 10 10 hrs. 320 85 3.0 x 10 14 hrs. 300 60 6.4 x 10 26 hrs. 250 16 4.0 x 10 3 days 250 16 9.0 x 10 4 days 200 0 1.3 x 10 11 days 200 0 1.4 x 10 30 days 200 0 9.4 x 10 100 days 200 0 2.0 x 10 (1) 367 days 167 0 8.2 x 10 (2) 600 volts applied between conductors throughout the test. Current of 1 amp/conductor throughout the test.
13
Figure 6 (Continued)
POST LOCA TESTS (IEEE STD. 383-1974)
(1) The LOCA test was continued at 200F, 0 psig and 100% RH for a total of 100 days. After the 100 day cycle, the cable was subjected to a post LOCA test consisting of 40x, 20x, 10x and 5x mandrel bends. The cable withstood a 5 minute 2200 volt dielectric test in water after each bend.
(2) The LOCA test was continued again at 167F, 0 psig and 100% RH for a total of 367 days. The cable then passed an additional post LOCA bend test of 40x and 2200 VAC for 5 minutes in water.
400 350 4 F 2 F 300 25(P I
200 167 F 150 100 0 0.1 5 10 50 100 500 1000 5000 10000 1IMR 'tNOVRS) 14
FIGURE 7 LOCA SIMULATION DATA Cable A ed to the E uivalent of 90C for 40 Years Thermal aging of 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> at 155C followed by 2 x 10 8 rads, gamma.
Cable Construction 2/C 416 AWG as in Figure l.
Test Re uirements Environmental Simulation Cycle per Appendix A, IEEE- Std. 323-1974, combined cycle for PWR/BWR.
Cable sprayed with 0.28 molar H BO solution adjusted to pH of 10.5 with NaOH for first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and wi%h mineral-free water continuously thereafter.
Test Results IR IR Cdr 01 Cdr 52 Pressure Megohms per Megohms per Temp. Psig 20 ft. test 20 ft. test Time OF Steam length length 0 75 0 7.0 x 104 8.0 x 10 End of 3 hrs. 340 110 6.2 x 101 7.2 x 10 4 hrs. 165 0 1.1 x 10 1.2 x 10 7 hrs. 340 110 .55 x 10 .55 x 10 10 hrs. 320 85 1.1 x 10 x 10 14 hrs. 300 65 3.0 x 10 2.9 x 10 4 days 250 20 2.0 x 10 1.7 x 10 17 days 200 0 7 ~ 7 x 101 7.6 x 10 45 days 200 8.4 x 10 8.8 x 10 104 days 200 0.7 x 102 4;0 x 10 144 days 167 1.0 x 10 1.7 x 10 161 days 167 0.6 x 10 (1) 0.7 x 10 (1) 600 volts applied between conductors and 345 volts between conductors and shield throughout the test. Current of 1 amp/conductor throughout the test.
15
Figure 7 (Continued)
POST LOCA BEND TEST (IEEE STD 383-1974)
(1) At the conclusion of the above 161 day cycle, the cable was removed from the autoclave and successfully withstood a 40x bend followed by 2400 VAC for 5 minutes immersed in water.
400
'350 4 F 300 25d' 200 150 100 0 0.1 5 10 50 100 500 1000 5000 10000 TIME (HOURS) 16
BIW FIGURE 8 LOCA SIMULATION DATA Cable Containin a S lice A ed to the E uivalent of 90C for 40 Years Thermal aging of 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> at 155C followed by 2 x 10 8 rads, gamma.
Cable Construction Conductor 1/C 412 AWG 7/.0305" tinned copper Insulation Ethylene propylene rubber, 30 mil wall, with BOSTRAD 7 CSPE jacket, 20 mil wall Splice Cable contained 1 splice insulated with Raychem WCSF flame retardant tubing Test Re uirements Environmental Simulation Cycle per Appendix A, IEEE Std. 383-1974, BWR cycle, Table A2.
Cable sprayed with 0.28 molar H3B03 solution adjusted to pH of 10.5 with NaOH for first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and with mineral-free water thereafter through the first 30 days only.
est Results IR Pressure Cdr Ground Tsmp o Psig Megohms per 20 ft.
Time F Steam test length 78 0 2~2 x 10 End of 3 hrs. 340 110 .45 x 10 6 hrs. 320 75 1.0 x 10'0 10 hrs. 300 50 1.9 x 4 days 250 20 .35 x 10'0 55 days 200 0 .8 x ill days 200 0 1.2 x 10 (1) 600 volts applied between conductor and ground throughout the test.
Current of 5 amps applied continuously throughout the test.
POST LOCA TEST (IEEE STD 383-1974) test continued at 200F, 0 psig and 100% RH for a The LOCA total of ill was subjected was days.
to a After the post LOCA ill test day cycle, the spliced cable consisting of a 40x mandrel bend. The cable and splice then withstood a 5 minute 2400 volt dielectric test immersed in water.
17
FIGURE 8 40(P 35(P 40oE 328 30d 25EI0Ot'E 0 0$ 5 10 50 100 500 1000 5000 T0000 TIME OIOUES)
VI I. FLAME RESISTANCE VERTICAL TRAY FIRE TESTS BOSTRAD 7E cables successfully pass the flame test requirements of IEEE Standard 383-1974, as shown in Figures 9 and 10. The 2/C and 7/C cables self-extinguish and do not propagate flame after a 70,000 BTUh gas flame is continuously applied to the cables for 20 minutes.
The excellent resistance of BOSTRAD 7E cables to burning is shown by the short distance of insulation damage and jacket char.
BOSTRAD 7E cables also pass the IEEE 383-1974 flame test requirements when a 210,000 BTUh burner is substituted for the 70,000 BTUh burner.
test.
Figure ll demonstrates the satisfactory performance in'his Aging does not adversely affect the flame resistance of the cables. This is shown by Figure 12, which describes the testing of a BOSTRAD 7E cable after thermal aging of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121C (equivalent to 40 years at 50C). Additionally, the oxygen index of the CSPE jacket has been recorded after thermal aging. When aged to a condition beyond projected 40 year life (refer to Figure 3), the CSPE jackets show an increase in oxygen index, indicating no degradation of flame resistance.
Condition Oxygen Index of chlorosulfonated ol eth lene 'acket Initial, unaged 35 Aged 300 hrs. 9 180C 40 19
FIGURE 9 VERTICAL TRAY FLAME TEST Cable Construction 2/C 116 AWG as in Figure l.
Test Re uirements -- IEEE 383-1974, Paragraph 2.5.
Vertical steel ladder type cable tray, 10 cables mounted 1/2 diameter apart 8'ong, 12" wide, 3" deep 10" wide, 70,000 BTU/hr ribbon burner, 1500F flame Flame time -- 20 minutes Gas source commercial gas Cable passes if flame does not propagate and cable self-extinguishes.
Test Results Im in ement Tem erature Min F Min F I Min oF Min QF 1500 1500 1500 1480 5
6 7
1440 1440 ll 10 12 1380 1380 1360 15 16 17 1360 1360 1400 1420 8 1400 13 1380 18 1460 1480 9 1400 14 1380 19 1400 20 1400 Time after I nition Time of burner ignition 0 min. 0 sec.
Time of burner shut-off 20 min. 0 sec.
Time flame extinguished 20 min. 0 sec.
Jacket ignition 1 min. 30 sec. (approx)
Distance of. jacket char 34 inches Distance of insulation damage 18 inches Cables test.
self-extinguished and did not propagate the flame passed Insulated conductors removed from the cable also passed the flame resisting test of ICEA S-19-81, Sec. 6.19.6.
20
BIW FIGURE 10 VERTICAL TRAY FLAME TEST Cable Construction 7/C N12 AWG as in Figure l.
Test Re uirements -- IEEE 383-1974, Paragraph 2.5 Vertical steel ladder type cable tray, 8'ong, 12" wide, 3" deep 12 cables: mounted 1/2 diameter apart 10" wide, 70,000 BTU/hr. ribbon burner, 1500F flame Flame time -- 20 minutes Gas source propane gas Cable passes if flame does not propagate and cable self-extinguishes.
Test Results Im in ement Tem erature Min F Min F I Min QF Min oF 1500 1460 1780 1600 1400
.1300 5
6 7
1600 1700 ll 10 12 1600 1600 15 16 17 1600 1600 1400 8 1700 13 1620 18 1620 1360 9 1760 14 1600 19 1660 20 1600 Time after I nition Time of burner ignition 0 min. 0 sec.
Time of burner shut-off 20 min. 0 sec.
Time flame extinguished 20 min. 0 sec. (immediately)
Jacket ignition 1 min. 45 sec. (approx.)
Distance of jacket char 16 inches Distance of insulation damage 0 inches Cables self-extinguished and did not propagate the flame passed test.
Insulated conductors removed from the cable also passed the flame resisting test of ICEA S-19-81, Sec. 6.19.6.
BIW FIGURE 11 VERTICAL TRAY FLAME TEST, AGED CABLES Cable Constructions 2/C 416 AWG and 4/C 416 AWG as described below.
Test Re uirements IEEE 383-1974, Paragraph 2.5 Vertical steel ladder type cable tray, long, 12" wide, 3" deep cables: mounted 1/2 diameter apart 8'2 10" wide, 70,000 BTU/hr. ribbon burner, 1500 flame Flame time 20 minutes Gas source propane gas Cable passes if flame does not propagate and cable self-extinguishes.
Conditionin Cables aged 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121C, equivalent to 40 years at 50C.
Test Results Time after I nition 2/C 116 AWG I 4/C 416 AWG Time of burner ignition 0 min. 0 sec. 0 min. 0 se Time of burner shut-of f 20 min. 0 sec. 20 min. 0 sec.
Time flame extinguished 20 min. 0 sec. 20 min. 0 sec.
Jacket ignition (approx) 1 min. 45 sec. 1 min. 45 sec.
Distance of jacket char 49 inches 47 inches Distance of insulation damage 36 inches 39 inches Cables self-extinguished and did not propagate the flame passed test.
Insulated conductors removed from the cables also passed the flame resisting test of ICEA S-19-81, Sec. 6.19.6.
Cable Constructions Conductors 516 AWG 7/.0192" tinned copper Insulation 20 mils ethylene propylene rubber with 10 mils BOSTRAD7 CSPE insulating jacket.
Shield Aluminum/polyester tape with 518 AWG 7/.0152" tinned copper drain wire Jacket 45 mils BOSTRAD 7 CSPE 22
FIGURE 12 VERTICAL TRAY FLAME TEST, AGED CABLE Cable Construction 2/C f16 AWG Test Re uirements IEEE 383-1974, Paragraph 2.5 Vertical steel ladder type cable tray, 8'ong, 12" wide, 3" deep 12 cables: mounted 1/2 diameter apart 10" wide, 70,000 BTU/hr. ribbon burner, 1500 flame Flame time -- 20 minutes Gas source propane gas Cable passes if flame does not propagate and cable self-extinguishes.
Cables aged 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 150C, equivalent to 40 years at 66C.
Test Results Time After I nition Time of burner ignition 0 min. 0 sec.
Time of burner shut-off 20 min. 0 sec.
Time flame extinguished 20 min. 24 sec.
acket ignition (approx) 1 min. 30 sec.
istance of jacket char 39 inches istance of insulation damage 24 inches Cables self-extinguished and did not propagate the flame passed test.
Insulated conductors removed from the cables also passed the flame resisting test of ICEA S-19-81, Sec. 6.19.6.
Cable Construction Conductors 416 AWG 7/.0192" tinned copper Insulation 25 mils ethylene propylene rubber with 15 mils BOSTRAD7 CSPE insulating jacket.
Shield Aluminum/polyester tape with 418 AWG 7/.0152" tinned copper drain wire Binder Flame retardant Jacket 45 mils BOSTRAD 7 CSPE 23
FIGURE 13 VERTICAL TRAY FLAME TEST, 210,000 BTU Cable Construction 7/C 414 AWG as described below Test Re uirements IEEE 383-1974, Paragraph 2.5 except 210,000 BTU/hr. burner and 15'ong tray Vertical steel ladder type cable tray, 15'ong, 12" wide, 3" deep 10 cables mounted 1/2 diameter apart 10" wide, 120,000 BTU/hr. ribbon burner, 1500F flame Flame time -- 20 minutes Gas source propane gas Cable passes if flame does not propagate and cable self-extinguishes.
Test Results Time after I nition Time of burner ignition 0 min. 0 sec.
Time of burner shut-off 20 min. 0 sec.
Time flame extinguished 20 min. 0 sec. (immediately)
Jacket ignition 1 min. 30 sec. (approx.)
Distance of jacket char 66 inches Distance of insulation damage 58 inches Cables self-extinguished and did not propagate the flame passed test.
Insulated conductors removed from the cable also passed the flame resisting test of ICEA S-19-81, Sec. 6.19.6.
Cable Construction Conductors 514 AWG 7/.0242" tinned copper Insulation 30 mils ethylene propylene rubber with 15 mils BOSTRAD 7 CSPE insulating jacket.
Jacket 60 mils BOSTRAD 7 CSPE 24
BIW FIGURE 14 VERTICAL TRAY FLAME TEST AGED CABLE g 2 1 0 g 000 BTU Cable Construction 2/C 416 AWG as described below Test Re uirements IEEE 383-1974, Paragraph 2.5 except 210,000 BTU/hr. burner and 15'ong tray Vertical steel ladder type cable tray, 15'ong, 12" wide, 3" deep 7 cables: mounted 1/2 diameter apart 10" wide, 120,000 BTU/hr. ribbon burner, 1500F flame Flame time 20 minutes Gas source -- propane gas Cable passes if flame does not propagate and cable self-extinguishes.
Conditionin Cables aged 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121C, equivalent to 40 years at 50C.
Test Results Time after I nition Time of burner ignition 0 min. 0 sec.
ime of burner shut-off 20 min. 0 sec.
Time flame extinguished 20 min. 42 sec.
Jacket ignition 1 min. 30 sec. (approx.)
Distance of jacket char 57 inches Distance of insulation damage 52 inches Cable self-extinguished and did not propagate the flame passed test.
Insulated conductors removed from the cable also passed the flame resisting test of ICEA S-19-81, Sec. 6.19.6.
Cable Construction Conductors 416 AWG 7/.0192" tinned copper Insulation 20 mils ethylene propylene .rubber with 15 mils BOSTRAD7 CSPE insulating jacket.
Shield Aluminum/polyester tape with 018 AWG 7/.0152" tinned copper drain wire.
Jacket 45 mils BOSTRAD 7 CSPE
VIII. LONG TERM WATER ABSORPTION BOSTRAD 7E cables have excellent moisture resistance as demonstrated by the stability of electrical properties after long term immersion in water. This is shown by Figure 13 for the electroendosmosis method in 90C water and by Figure 14 for EM-60 tests in 75C water.
FIGURE 15 LONG TERM ACCELERATED WATER ABSORPTION ELECTROENDOSMOSIS METHOD IN 90C WATER A potential of 600 volts DC negative was continuously applied to the, conductor except while measurements were being performed.
Conductor fjl4 Ethylene AWG 7/.0242" tinned copper Insulation propylene rubber, 30 mil wall covered with BOSTRAD 7 CSPE, 15 mil wall TIME SIC POWER FACTOR, 8 3300 VAC FOR 5 MIN.
1 day 3.4 3.2 pass 1 week 3.4 2.3 pass 2 weeks 3.4 2.1 pass 4 weeks 3.5 1.4 pass 8 weeks 3.5 1.6 pass 12 weeks 3.6 1.5 pass 16 weeks 3.8 1.7 pass 20 weeks 3.7 1.7 pass 24 weeks 3.7 1.4 pass 26 weeks 3.8 1.8 pass 28 weeks 3.8 1.8 pass 32 weeks 3.8 1.9 pass 36 weeks 3.9 1.6 pass 40 weeks 3.9 2.0 pass 44 weeks 4.0 2.0 pass 48 we'eks 4.0 3.0 pass 26 0
BIW FIGURE 16 LONG TERM ACCELERATED WATER ABSORPTION ICEA S-68-516 ELECTRICAL METHOD EM-60 Conductor 416 AWG 7/.0192" tinned copper Insulation Ethylene propylene rubber, 30 mil wall Water Temperature -- 75C Increase Stability Insulation Time In Ca acitance (8) Factor (8) Resistance Megohms er 1000 feet 1 day 0.10% 7.9 x 10 7 days 0.14 0.10 1.3 x 10 14 days 0.14 0.10 1.6 x 10 4 weeks 0.29 0.10 2.0 x 10 8 weeks 0.86 0.10 2.3 x 10 12 weeks 0.72 0.04 2.3 x 10 16 weeks 1.43 0.10 3.2 x 10 3
20 weeks 1.29 0.10 2.7 x 10 24 weeks 1.40 0.06 2.8 x 10 28 weeks l. 57 0.03 4.0 x 10 32 weeks 2. 00 0.10 4.0 x 10 36 weeks 2. 14 0.00 4.0 x 10 40 weeks 2. 00 0.03 2.5 x 10 44 weeks 2. 14 0.05 3.0 x 10 48 weeks 2. 57 0.06 3.3 x 10 3 52 weeks 2.57 0.07 4.0 x 10 I
27
l RG6E Reference 83-1 KANT WO T~ NVCIIARP4NSIIY ENGINEERING ANALYSIS AND TEST COMPANY, INC.
4676 ADMIRALTY WAY MARINA DEL REY, CALIFORNIA 90291 (213) 822-0931 TEST REPORT IEEE-323-1974 QUALIFICATION OF DELPHI IV HYDROGEN ANALYZER I,[
As ManufactureQ By COMSIP DELPHI, INC.
Prospect: 1035-1 Date: December 1980 SPECIALIZED ENGINEERING SERVICES> NUCLEA ~ ENGINEERING MECHANICAL ENGINEERING ~ EARTHGUARE ENGINEERING STRUCTURAL DYNAMICS ~ COMPONENT OUALIF ICATION SOT TIN ARE D EV ELOPMENT
ENGINEERING ANALYSIS AND TEST COMPANY, INC.
4676 ADMIRALTY WAY MARINA DEL REY, CALIFORNIA 90291 (213) 822-093 I CERTIFICATE EA&T Company Inc. dba Engineering Analysis and Test Company performed an environmental qualification test program on a Delphi IV Hydrogen Analyzer prototype manu-factured by Comsip Delphi, Inc. of South El Honte, Cali o'rnia.
4 The qualification program was performed in conformance with EAST Test Plan, Pro ject No. 1035-1 Rev. 2 dated November 19 79 and IEEE-32 3-19 74 Standard entitled " IEEE
~
Standard for Qualifying Class 1E Equipment for Nuclear
'ower Generating Stations",, as implemented by Nuclear Regulatory Guide 1.89 entitled "Qualification of Class lE Equipment for Nuclear Power Plants".
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@~TIVE PF Raym d Perez M chael Perez Pro ssional Engine Quality Assurance 5tf CIAL IZED f NGINffEING SERVICES> NUCLEAR ENGINEERING MECHANICAL ENGINEERING ~ EARTHQUAKE ENGINEERING STEUCTUEAL DYNAMICS ~ COMPONENT GUALIIICATION SOFTWARE DEVELOPMENT
TABLE OF CONTENTS 1.0 Purpose 2.0 Scope 3.0 Definitions 4.0 Procedure 4.1 General 4.2 Functional Tests 4.3 Inspection and Operational Tests 4.4 Service Condition Simulation and Aging 4.5 Irradiation 4.6 Seismic Vibration 4.7 Simulated Post Accident Condition 4.8 Failure Analysis Criteria 4.9 Acceptance Criteria 5.0 Qualification Test Results 5.1 Summary Appendix A List of Safety Related Xnstruments Appendix B Inspection and Instrument Operational Test Results Appendix C Delphi ZV Hydrogen Analyzer Functional Test Procedure and Results Appendix D Service Condition Simulation Aging
/
Appendix E Seismic Qualification Appendix F Simulated Post Accident Conditions Appendix G Calibration Data Appendix H References
- l. 0 PURPOSE To describe the procedure which was utilized for the environmental qualification type testing of safety related instruments for nuclear power plant applications.
2.0 SCOPE This procedure applies to safety related instruments for which project specifications require their quali-fication in accordance with the requirements of IEEE-3g3-1974 Standard For Qualifying Class lE Equipment For Nuclear Power Generating Stations, as implemented by Regulatory Guide 1.89, Qualification of Class lE Equipment For Nuclear Power Plants.
3.0 DEFINITIONS 3.1 Safet Related Instruments Instruments that are essential to emergency reactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal, or otherwise are essential in preventing signifi-cant release of radioactive material to the environment.
Tests made on one or more sample instruments to verify adequacy of design and manufacturing processes.
3.3 RAD (Roent en - Absorbed Dose)
Absorption dose of 100 ergs/gm (material). The rad is a measure of radiated energy absorption of. any form (particle or electromagnetic) in any material.
3.4 Octave The interval between two frequencies whiwh have a frequency ratio of two.
r, 3.5 0 eratin 'Basis Earth uake (OBE)
That earthquake which produces the vibratory ground motion for which those features of the nuclear power plant necessary for continued operation without undue risk to the health and safety of the public are designed to remain functional (excerpted from IEEE-Std. 344-1975).
3.6 Safe Shutdown Earth uake (SSE)
That earthquake that produces the maximum vibratory ground motion for which certain structures, systems, and components are designed to remain functional.
4.0 PROCEDURE 4.1 General
- 4. 1.1 The procedure which was followed outlines a generic environmental plan developed to qualify the Delphi Model K Hydrogen Analyzer as manu-factured by Comsip Delphi, Inc. for nuclear power plant installation. The procedure describes the type tests, which were performed on the instruments in a specific order. The sequence used is the one recommended by the IEEE-323-1974 Standard and briefly consists of: ~"
[
4.1.1.1 Inspection and Operational Tests 4.1.1.2 Functional Tests
- 4. 1. 1. 3 Thermal Aging 4.1.1.4 Functional Tests 4.1.1.5 Mechanical Cycling 4.1.1.6 Functional Tests 4.1.1.7 Irradiation 4.1.1.8 Functional -Tests 4.1.1.9 Seismic Uibration 4.1.1.10 Functional Tests 4.1.1.11 Simulated Post Accident, Condition 4.1.1.12 Functional Tests 4.1.1.13 Final Inspection and Operational Tests 4.1.2 The type tests were applied to one i~nstrument from each different fami1y. Design verification
d oe s not require that more than one unit be tested. The instrument tested vas a random 1 y selected production model. All of the different tests and conditions vere applied to the same instrument. Appendix A of this procedure lists all of the different instruments which were subjected (one unit of each) to type tests.
4.1.3 developing this procedure various documents, a'n NRC Regulatory Guides, IEEE Standards etc.,
vere consulted. Appendix G of this procedure lists all references.
- 4. 1.4 Unless otherwise specified herein, all tests described by this procedure were performed at an atmospheric pressure of 29.92 + 2.0 inches of mercury absolute, a temperature of 70 + 10 F and a relative humidity of 50 per-cent + 25 percent.
4.l.5 Instruments were mounted in a manner and position that best simulates the expected xns t a llation. The environmental exposures a
and instrument performance vere mons o red't using equipment that provides resolution for the detection of meaningful changes in the measured variables. For the LOCA exposure 1 th instruments were mounted in a NEMA
, 12 caSinet. For seismic vibratxon only,
'nstruments were mounted on a rigid test fixture. For all other tests, simulate d mounting was not required.
- 4. 1.6 Measuring devices and test equipment utxlxzed in .the performance of the type tests were calibrated utilizing reference standards
( or x'nterim standards) whose calibration had been certified by being traceable the National Bureau of Standards. All re-,
ference standards utilized in measuring component, parameters and all test equipment calibration vere supported by certificates, reports, or data sheets attesting to the data, accuracy, and conditions under which the results furnished were obtained.
4.2 Functional Tests 4.2.1 The ability of the complete Delphi Hydrogen Analyzer System to perform its Class lE function was demonstrated by the performance of functional tests. These tests were per-formed initially in the program to develop a data base.and were then programmed following each environmental exposure. The'functi'onal test procedure, and test results are des-cribed in Appendix C.
4.2.2 .Functional tests performed extend, as a minimum, to a simulation of Class 1E performance under normal condita.ons.
Results and data obtained from functional testing were used as a base for comparison with performance under more highly stressed conditions.
4.3 Ins ection and 0 erational Tests 4.3.1 Instruments were subjected to inspection and operational tests to assure that there was no damage due to handling since manu-facture and to verify that their performance was in accordance with equipment and project'.
specifications. All inspections and operational
'tests'ere performed in accordance with written procedures and the test results were developed, documented and controlled in accordance with EA&T Company Inc.'s Quality Assurance Manual.
Inspection and operational test results for the 'instruments are presented xn Appendix B of this report.
4.3.2 The equipment was operated to the extremes of all performance and electrical character-istics given in the equipment specifications.
Included in the equipment specification is the requirement for operation of the instru-ments at 110 V + 10%.
~l 4.4 Service Condition Simulation and A in 4.4.1 The objective of aging was to put the instruments in a condition equivalent to their end-of-life condition in order to verify that they would perform their function after being subjected to normal
'nvironments during their, design life.
4.4.2 These type test exposures may be catagorized in two phases. The first. phase consisted of exposure to elevated temperature to simulate the effects of chemical reactions on the materials over the design life.
The second phase consisted of accelerated operational cycling of instruments to simulate the expected mechanical wear and electrical contact degradation of the instruments being tested.
Table D-I of Appendix D of this procedure provides a schedule of the design life, baseline temperature, aging time, and aging temperature under which thermal aging was performed.
Table D-XI of Appendix D of this procedure lists all instruments, the number'nd rate af, cycles as well as comments on how
- cyclingiwas performed on parameters which are directly related to the operation of each instrument.
4.4.3 At the completion of the Service Condition Simulation and Aging, the Delphi IV Hydrogen Analyzer System was inspected and functionally tested and results were docu-mented as described in paragraph 4.2 above.
Performance data was compared with that which was previously obtained.and any de-viations were evaluated.
4.4.4 Thermal Aging temperatures li~sted i~n Table D-I of Appendix D were established'ased on material specifications as provided by the manufacturer, the baseline temperature of the instruments, an assumed design life of 5 or 10 years and the 10'C rule.
4.5 Irradiation 4.5.1 The objective of the irradiation exposure was to subject the test instruments to radiation doses anticipated in the design life, and as a minimum, one Design Basis Event. The irradiation test dose was the total of. normal and abnormal doses.
4.5.2 Irradiation was performed in a radiation chamber with Co-60 source pencils. The exposure was of Gamma radiation.
4.5.3 The components were arranged in the chamber and then the chamber was loaded with Co-60 so urce pencils.~ The chamber temperature was maintained at approxima'tely 70 P annd the pressure was one atmosphere. The dose rate was limited to less than 1.0 Nrad/hour.
After the irradiation tests were completed, the system was functionally tested as described in paragraph 4.2 above.
4.5.4 The total integrated service life radiation dose varies with instrument location in the Nuclear Power Plant. The radiation dose to the Delphi K-IV Hydrogen Analyzer for this generic <environmental plan is given in
'Table'D-'III of Appendix D.
4.5.5 The total integrated service life radiatxon
~ ~
dose is the sum of the normal in-service radiation exposure and the post accident. in-service radiation exposure.
4.6 Seismic Vibration of Seismic Vibration was to 4.6.1 The
'fobjective y, th t the operation of the instruments would not be impaired, when subgecte o minimum of five (5) Operating Basis Earth-quakes (OBE), fo 1 lowed by one p.) Sa fe Shut-down Earthquake (SSE).
The test items 'rimary mounting point was the normal mounting attachment provided on the test items which simulates the actual in-service mounting. The test items were a'ttached to a rigid fixture (natural frequency 33 cps) and then the fixture was attached to the exciter shake table. The fixture was designed to transmit the vibratory inputs without, any degradation to seismic require-ments as well as, to maintain the test item in its correct attitude.
Testing consisted of vibration inputs in two axes simultanously and independently
-such that a purely rectilinear motion does not result. During the two axes simultaneous vibration, testing was conducted in the following configuration:
Vertical Horizontal (longitudinal)'l axis Vertical - Horizontal (lateral) N2 axis A continuous sine wave resonance search was conducted in each axis. The rate of change of frequency (1 Hz to 40 Hz) was approximately one octave per minute, or that frequency change necessary to acquire suitable response. The input level was 0.2 g peak. Only one axis at a time had vibration applied.
Seismic Qualification was performed using a complex random motion. Testing.was performed in two steps with the test items principal horizontal axis first positioned parallel with the test table motion, then rotated 90 in the horizontal plane for the second step.
The test items were sub)ected to 5 O.B.E. I s of not less than 30 seconds each and 1 S.S.E.
of not less than 40 seconds.
In establishing the required input acceleration, the following considerations were given. The test instruments are panel mounted. Therefore, the required response motion for all directions
l was that shown in Figure E-1 for Generic Qualification. The test response spectra enveloped the required response spectra to the extent capable, given limitations, of the test table.
4.6.6.1 The Control Panel was seismically
.qualified to IEEE-344-1975 Sec. 7.2 by a combined test and The test report documenting analysis'rogram.
this program is EAST Report No. -1035-2, dated July 1980. The Required:Response Spectrum for all directions is shown in Figure E-II of Appendix E of this report.
4.6.6.2 The test instruments were mounted on the shake table in a manner that dynamically simulated the recommended mounting. If the instrument was in-tended to be mounted on a control panel, the response at the instrument mounting location was monitored during an assembled control panel sine sweep test and the instrument was mounted directly to the shake table with the in-service excitation simulated.
4.6.7
'oA control accelerometer was mounted ea'ch'input mounting point.
adjacent 4.6.8 During the performance of the seismic tests, the control accelerometers and response accelerometers were permanently recorded.
The control accelerometers output for the complex random tests was routed through a shock spectrum analyzer and the data presented as a peak response of frequency.
4.6.9 All instruments were energized (as applxcable) during the performance of the seismic tests.
Output response ('such as pressure, current, position, etc.) was monitored throughout the tpressure es t Relays hand switches, temperature and switch contacts were monzto red for
I chattering using a chatter detector with a chatter gate time of 1 msec.
4.6.10 Upon completion of the seismic vibration tests all instruments were functionally tested and results were documented as des-cribed in paragraph 4.2 above. Performance data was compared with that which was and any deviations were evaluated.
previously'btained 4.7 Simulated Post Accident Condition 4.7.1 The objective of this environmental exposure was to verify the capability of the equipment to operate under a postulated Design Basis Accident. The Simulated Post Accident, Condition exposure consisted of exposure to radiation, pressure, temperature and humidity. The post accident exposure to radiation was combined with the expected in-service radiation exposure as described in paragraph 4.5 Irradiation.
- 4. 7.2 The Simulated Post Accident Condition exposure was performed in a controlled environmental chamber. Appendix F lists the test." variables ('i.e., temperature,
'humidity,'ressure) and time profile.
4.7.3 All instruments were periodically monitored during the performance of these tests, Upon completion, the K-IU Hydrogen Analyzer was functionally tested and results pere recorded as described in paragraph 4.2.
4.7.4 The instruments and equipment were mounted and connected in a manner that simulated their installation when in actual use.
Throughout the LOCA Post Accident Condition exposure, the venting path of all pneumatic devices were via all components that are installed during normal operation.
4.7.5 The K-IV Hydrogen Analyzer withdrew a sample gas simulating its actual operation under a postulated Design Basis Accident. The sample gas temperature and pressure are indicated in Table F-l.
4..8 Failure Anal sis Criteria
- 4. 8.1 In the evaluation of the qualification test results, any sample equipment was assumed to have failed when the equipment did not perform Class 1E functions required by the
-equipment specifications.
4.8.2 If a failure occurred during the qualification test process, this did not necessarily con-stitute a failure to qualify. It has to be determined whether the failure was random or an end-of-life failure. True random failures by definition do not impact qualified life.
4.8.3 If end-of-life or random failure was established as the cause of failure, a replacement plan was to be initiated for the component which failed if such replacement was feasible. If such replacement was not feasible, then the equip-ment was considered to have reached end-of-life.
- 4. 8;. 4 If th8,4as'o
'lan Appropriate component replacement be implemented, the qualified life of the equipment'as not degraded.
4.9 Acce tance Criteria 4.9.1 To meet, the provisions set forth by IEEE-323-1974, the qualification program was to be accompanied by a detailed report docu-menting all the tests, data, etc., and the
. acceptance.
4.9.2 The acceptance criteria for Service Condition Simulation and Aging exposure was the suc-cessful simulation of the design life. The D e lphi IV Hydrogen Analyzer was required to perform after the simulated accelerate d aging process without the loss of Class lE function and structural integrity.
4.'9. 3 The a'cceptanc'e criteria for Simulated Post...,
Accident Condi;tions exposure required that loss of Class lE performance did not occur, loss of input and output did not occur, structural integrity be maintained, and spurious signals were not produced. The addition of setpoint securing devices were not to aid in maintaining setpoint accuracy.
4.9.4 The acceptance criteria for Seismic exposure required that structural integrity he main-tained, and that loss of Class. 1E performance did not occur during or after the excitation of one Safe Shutdown Earthquake and five Operating Basis Earthquakes.
4.9.5 A qualification report, was to be prepared and certified by a registered professional engineer. The report was to contain all the detailed test procedures, measurements, description of test instrumentation, fixtures,
- calibration data and interpretations, and data on, and explanation of any anomalies.
The qualified life of the particular component instruments was to be delineated as the period of time for which satisfactory performance could be demonstrated for the specified se of service conditions.
5.0 Qualification Test Results 5.1 Summary The sequence of'environmental qualification type tests performed on the Delphi IV Hydrogen Analyzer prototype was completed on 10/26/80, at the con-clusion of the 100 day Post LOCA exposure.
\ /
Two anomalies were observed as a result of these tests.
At the 42nd day of the Post LOCA exposure, the Sample Pump bearings were observed to be fixed, preventing the actuator arm from moving. The bearings were replaced and the pump resumed operation. The reason for this occurance is under investigation. It has not been determined whether the causal factor was random or end of life.
Following the 100th day of Post LOCA exposure the Sample Pump diaphrams were observed leaking.
This anomaly is also under investigation.
is currently unknown whether the leakage is the It result of random or end of life conditions.
Operational tests of the individual components will be performed at a later date. The Hydrogen Analyzer unit has not been dissassembled at this time,,so that interested observers may witness the unit'.s functional operation.
Functional test results are presented in Appendix C.
APPENDIX A LIST OF SAFETY RELATED INSTRUMENTS
TABLE A-1 List Of Safety Related Instruments Item Description Entry Exit Valve Hoke Model 4251 G6Y Serial No. 2190 Moisture Separator Armstrong Model ll-AV Serial No. 1793 Gas Manifold
. Serial No. 3 Air Cooled Heat Exchanger Serial No. 4 Flowmeter Brooks Model 1350 Tube No. 196A Serial No. 2189-5 Flowmeter Brooks Model 1350 Tube No. 5-65A" Serial No. 2189-, 6 Pressure Indicator Marshalltown Model 52B Serial No. 0195 Sample Pump Serial No. 1882 H2 Analyzer Serial No. 371 10 Analyzer Electronics Serial No. 10 Flow Orifice Serial No. 3356 14-
TABLE A-1 List Of Safety Related Instruments (continued)
Item Description 12 A&B Differential Pressure Switch Static 0-Ring Model No. 15R3-K2-VYIC Serial No. 78-4-1097 13 Down Stream Regulator Conoflow Model H21XT-XXX Rl Serial No. 3204-15 14 Down Stream Regulator Conoflow Model H21XT-XXX R2 Serial No. 3204-16 15 Down Stream Regulator Conoflow Model H21XT-XXX R3 Serial No. 1791 16A Down Stream Regulator Conoflow Model H21XT-XXX-RB Serial No. 2191-16A 16B Down Stream Regulator Conoflow Model H21XT-XXX-RB Serial No. 2191-16B 17 Calibration 6 Reagent Valve ASCO Catalog No. THT8262C7E Serial No. 93415D 18 A,B, Check Valve C NUPRO Model SS-4CA-3 Serial No. 2187 19 Temperature Switch Fenwall Model 22800 Serial No. 7901 20 Temperature Bulb Fenwall Model 22800 Serial No. 21918
TABLE A-1 List Of Safety Related Instruments {continued)
Item Description 21 Lights GE Model Et-16 Serial No. 0165A7844P5 Relay Potter Brumfield Model KRPllAG Serial No. 174414 23 Relay Potter Brumfield Model KRP14AG Serial No. 173308 Relay GE Model CR2810A 14AJ Serial No. 22D135 25 Magnetic Motor Starter GE Model CR206BO Serial No. 15D21G2 26 Switch GE Model CR2940U201 Serial No. 26: .~.
27 Terminal Strip GE Model EB5 Serial No. 27 28 Circuit Breaker ITE Pushmatic Model P1515 Serial No 614 29 Fittings Hoke Gyrolok Model 6CM6-316 Serial No. 29 30A Cal Rod Strip Heater {4 EA)
GE Model 2A907A102 Serial No. SS2041-30A 30B Cal Rod Strip Heater {4 EA)
GE Model 2A907A102 Serial No. SS2041-30B
TABLE A-1 List Of Safety Related Instruments (continued)
Item Description 30C Cal Rod Strip Heater (4 EA)
GE Model 2A907A102 Serial No. SS2041-30C 30D Cal Rod Strip Heater (4 EA)
GE Model 2A907A102 Serial No. SS2041-30D 31 Sample Pump Motor (1)
Reliance ID No. 1YF882640AZO NE Serial No. 31 Current Transmitter AGM Model CD-4000 Serial No.38-320 33 Trip Switch AGM Model CD-4004-1 Serial No.38-213
.- 34 Matheson Flowmeter Tube'o. 600 !.> (.
Serial No. 34 35 Matheson Flowmeter Tube No. 601 Serial No. 35 36 Flowmeter Brooks Model 1350 Tube No. 459 Serial No. 36 37A Terminal Strip Allied Barrier Block Model 750R1503 Serial No. 37A 37B Terminal Strip Allied Barrier Block Model 750R1503 Serial No. 37B Note: (1) Sample Pump Motor is purchased as prequalified to IEEE-323-1974 by manufacturer.
TABLE F-I SIMULATED POST ACCIDENT CONDITIONS DELPHI IV HYDROGEN ANALYZER GENERIC QUALIFICATION I
LOCA Ambient Conditions At Control Cabinet Location Time, Days Temperature, C '%-100 66 (150'F)
Pressure, in Hg 29.92 + 2 Relative Humidity, 90+ 5 LOCA Ambient Conditions at Sample Nithdrawn Point Time Pressure 0-15 Min. N/A N/A 15 Min. 10 Hours 150 C (300 F) 483 KPA (70 PSI) 10 Hours - 4 Days 99 C (210 F) 276 KPA (40 PSI) 4 Days 100 Days 75 0C (167 0F) 35 KPA (5 PSI )
NOTE: All specified parameters include margins of
+ 8 C (15 F) for temperature, + 10% of gauge pressure and + 10% of period of time equipment is qualified to operate following design basis event.
At 10 HRS, 4 Days then every 10 Days thereafter investigate readout 8 4.5% H~ in air then in steam at. hist'ogram poi"nt<
'g NOTE: Instruments mounted in simulated NEMA 12 Cabinet.
60 PSI back pressure on Comsip Delphi Supplied Boiler System.
lRGEE Reference 83-p
+>way>is ~e ms < ~nrrh y (~p+rf 7857 'g~-g ex- nwv prus rute- o~+c.ir- ic+rrv4 SopP<8<gvT'R)'~ o i efYHoC e> ~Ac-y ZCrC. Sdrrc c C
.gc r1P ~ac (W ) P~~4 ~ ~~4 Yaw~ SPS ~S )c rrz ~O y~~c7 -S'.r ~b-.g ABSTRACT c, 8 r i Vg z
/
This final test report describes the qualification test procedures and test results which were performed on the Hydrogen Analyzer Sample Pump for the Hydrogen Analyzer Systems K-III and E-IV.
A prototype of this pump was previously subjected to an environmental qualification test sequence during which certain anomalies were observed (see FAST Test Report 1035-1, dated September 1981). Subsequently, the Hydroqen Analyzer Sample Pump was subjected to supplemental IREE-323-1974 environmental type tests described in this report.
TABLE OF CONTEXTS 1.0 Purpose 2.0 Scope 3.0 Definitions 4.0 Procedure 4.1 General 4.2 Functional Tests 4.3 Inspection and Operational Tests 4.4 Service Condition Simulation and Aging 4.5 Irradiation 4.6 Seismic Vibration 4.7 .Simulated Post Accident Condition 4.8 Failure Analysis Criteria 4.9 Acceptance Criteria 5.0 Qualification Test Results
- 5. 1 Summary Appendix A List of Safety Related Xnstruments Appendix B Xnspection and Instrument Operational Test Procedure Appendix C Delphi IV Hydrogen Analyzer Functional Test Procedure Appendix D Service Condition Simulation Aging Appendix E Seismic Qualification Appendix F Simulated Post Accident Conditions Appendix G References 11
0
- 1. 0 PURPOSE To describe the procedure which was utilized for the environ-mental qualification type testing of safety related instruments for nuclear power plant applications.
2.0 SCOPE This procedure applies to safety related instruments for which project specifications require their quali-fication in accordance with the requirements of "IEBE-323-1974 Standard For Qualifying Class lH Equipment For Nuclear Power Generating Stations", as implemented by Regulatory Guide 1.89, "Qualification of Class 1E Equipment For Nuclear Power Plants." This procedure is in accordance with the guidance of NUREG-0588 "In-terim Staff Position on Environmental Qualification of Safety Related Electrical Equipment," dated September
~,A3 1979.
3.0 DEFINITIONS 3.1 Safet Related Instruments Instruments that are essential to emergency reactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal, or otherwise are essential in preventing signifi-cant release of radioactive material to the environ-ment.
IAJ Tests made on one or more sample instruments to verify adequacy of design and manufacturing processes.
- 3. 3 R~AD Roent en - Absorbed - Dose)
Absorption dose of 100 ergs/gm (material), The rad is a measure of radiated energy absorption of any form (particle or electromagnetic) in any material.
3.4 Octave The interval between two frequencies which have a frequency frequency ratio of two.
~
- 3. 5 0 eratin Basis Earth uake (OBE)
That earthquake which produces the vibratory ground motion for which those features of the nuclear power plant necessary for continued operation without undue risk to the health and safety of the public are designed to remain functional (excerpted from IEEE Std. 344-1975).
3.6 Safe Shutdown Earth uake (SSE)
That earthquake that produces the maximum vibratory ground motion for which certain structures, systems, and components are designed to remain functional.
- 4. 0 ~QDURF.
4.1 General The Hydrogen Analyzer Sample Pump extracts sample gases from points within the containment 'building for Hydrogen gas concentration determination. The pump is a small reciprocating dual stage unit. The pump is powered by a 1 Hp electric motor. The normal, abnormal and design basis accident conditions to which this pump will be subjected are identified in this section of the Test Plan.
4.1.1 The procedure which was followed outlines a generic environmental plan developed to qualify the Delphi Model K Hydrogen Analyzer Sample Pump as manufactured by Comsip,Inc. for nuclear power plant installation. The procedure describes the type tests to be performed on instruments in a specific order. The sequence used is the one recommended by the IEEE-323-1974 Standard and briefly consists of:
- 4. l. 1.1 Inspection and Operational Test 4.1. 1.2 Functional Tests
'4. l. 1.3 Thermal Aging 4.1. 1,4 Functional Tests 4.1. 1.5 Mechanical Cycling 4,1. 1.6 Functional Tests
- 4. l. 1.7 Irradiation 4.1. 1.8 Functional Tests 4.1 1.9
~ Seismic Vibration 4.1. 1.10 Functional Tests 4.1. 1.11 Simulated Post Accident Condition 4.1. 1.12 Functional ~ests
- 4. l. 1.13 Final Inspection and Operational Tests 4.1.2 Appendix A of this procedure list the five sample pumps which were tested, and describes the previous environmental testing performed on Sample Pump No. 1 b1otor, Reliance I.D.
No. IYF 882640A20 NE.
4.1.3 In developing this procedure various documents, NRC Regulatory Guides, IEEE Standards, etc.,
were consulted. Appendix G of this procedure lists all references.
4.1.4 Unless otherwise specified herein, all function-al tests described by this procedure were per-formed at an atmospheric pressure of 29.92 + 2.0 inches pf mercury absolute, a temperature of 70 + 10 F and a relative humidity of 50 percent
+ 25 percent.
4.1. 5 The Sample Pump was mounted in a manner and position that best simulates the expected in-stallation. The environmental exposures and in-strument performance were monitored using equip-ment that provides resolution for the detection of meaningful changes in the measured variables.
4.1.6 Measuring and test equipment utilized in the performance of the type tests were calibrated utilizing reference standards (or interim standards) whose calibration had been certified by being traceable to the National Bureau of Standards. All reference standards utilized in measur'ing and all test equipment calibration is supported by certi-ficates, reports, or data sheets attesting to the data, accuracy, and conditions under which the results furnished were obtained.
- 4. 2 Functional Tests 4.2.1 The ability of the Delphi ffydrogen Analyzer Sample Pump to perform its Class lE function was demonstrated by the performance of functional tests. These tests were performed initially in the program to develop a data base and then following each environmental exposure. The functional test procedure is described in Appendix C.
4.2.2 The functional tests performed extend, as a minimum, to a simulation of Class lE performance under normal conditions, Results and data obtained from functional testing was used as a base for comparison with performance under more highly stressed conditions.
4.3 Ins ection and Operational Tests 4.3.1 The Sample Pump was subjected to inspection and operational tests to assure that there was no damage due to handling since manufacture and to verify that its performance was in accordance with equipment and project specifi-cations. All inspections and operational tests were performed in accordance with written procedures and the test results were documented. Inspection and test procedures were developed, documented and controlled in accordance with EA&T Company, Inc.'s Quality Assurance manual.'nspection and operational test procedures for the instruments are presented in Appendix B of this procedure.
4.3.2 The Sample Pump was operated to the extremes of all performance and electrical characteristics given in the equipment specifications.
4.4 Service Condition Simulation and A in 4.4.1 The objective of aging is to put instruments in a condition equivalent to their end-of-service-life condition in order to verify that they shall perform their function after being subjected to normal environments during their design life.
4.4.2 These type test exposures may be categorized in two phases: The first phase consisted of exposure to elevated temperature to simulate the effects of chemical, reactions on the materials over the design life. The second phase consisted of accelerated operational cycling of instruments to simulate the expected mechanical wear and electrical surge degradation of the instruments being tested.
Table I of Appendix D of this procedure provides a schedule of the design life, baseline tempera-ture, aging time, and aging temperature under which thermal aging was performed.
Table II of Appendix D of this procedure lists all instruments, the number and rate of cycles as well as comments on how cycling was performed on parameters which are directly related to the operation of each instrument.
4.4.3 At the completion of the Service Condition Simulation and Aging, the Delphi IV Hydrogen Analyzer Sample Pump was inspected and functionally tested and results were docu-mented as described in paragraph 4.2 above.
Performance data was compared with those that were previously obtained and any deviations were evaluated.
4.'4. 4 Thermal Aging temperatures listed in Table I of Appendix D were established based on material specifications as provided by the manufacturer, the baseline temperature of the instruments, an assumed design life of 5 or 10 years for the pump diaphrams and pump bearings, respectively. Arrhenius Methodology was used to establish aging temperatures.
4.5 Irra8iation
- 4. 5. l The objective of the irradiation exposure was to subject the test instruments to radiation doses anticipated in the desiqn life,'nd as a minimum, one Design Basis l'.vent. The irra-diation test dose was the total of normal and abnormal doses.
4.5.2 Irradiation was performed in a radiation
,chamber with Co-60 source pencils. The exposure was of Gamma radiation.
4.5.3 The Sample Pump was placed in the chamber and then the chamber was loaded with Co-60 source pencils. The chamber temperature was at approximately 70 F and the pressure was one atmosphere. After the irradiation tests were completed, the system was functionally tested as described in paragraph 4.2 above.
4.5.4 The total integrated service life radiation dose varies with instrument location in the Nuclear Power Plant. The radiation dose given to the Hydrogen Analyzer Sample Pumps for this generic environment plan is stated in Table III of Anaendix D.
4.5. 5 The total. integrated service life radiation dose is the sum of the normal in-service radiation exposure and the post accident in-service radia-tion exposure.
4.5.6 To account for any effects unique to beta radiation',
one iaphragm was additionally exposed to beta radiation as indicated in Table III of Apped>dix D.
4.&- Seismic Vibration
- 4. 6.1 The objective of Seismic Vibration was to vverif r1y th at the operation of the instruments was not impaired, when subjected to a minimum of f ive (5) Operating Basis Earthquakes (OBE), followed by one (1) Safe Shutdown Earthquake (SSE).
4.6.2 The Sample Pumps primary mounting point was the normal mounting attachment provided on the test items which simulate the actual in-service mounting. The Sample Pump was attached t 0 a rigid fixture (natural frequency > 33 cps) and then the fixture was attached to the exciter shake table. The fixture was designed to transmit the vibratory inputs without any de-gradation to seismic requirements, as well as, to maintain the test item in its correct attitude.
4.6.3 Testing consisted of vibration inputs in two axes simultaneously and independently such that a purely rectilinear motion did not result.
During the two axes simultaneous vibration, testing was conducted in the following configura-t1on.
Vertical - Horizontal (longitudinal) 41 axis Vertical Horizontal (lateral} g2 axis 4.6.4 A continuous sine wave resonance search was conducted in each axis. The rate of change of frequency (1 Hz to 40 Hz) was approximatel y on e octave per minute, or that frequency change necessary to acquire suitable response. The input level was 0.2g peak. Only one axis at a time had vibration applied. Transmissi-bility plots were obtained and recorded for each orthogonal mounting orientation (i.e ~
longitudinal, lateral and vertical directions).
The transmissibility plots show in amplitude the ratio of the response of an accelerometer mounted near the center of gravity of the pump to the input as measured by an accelerometer mounted on the table for each of the three orthogonal axes.
Seismic qualification was performed using a complex random motion. The frequency content and range of input waveform was displayed as Test Tesponse Spectra (TRS) Shock Response Spectrum for both the Operating Basis Earth-quake (OBE) and Safe Shutdown Earthquake (SSE) for all three orthogonal axes. Testing was performed in two steps with the test horizontal axis first positioned items'rincipal parallel with the test table motion, then rotated 90 in the horizontal plane for the second step.
The Sample Pump was subjected to 5 O.B,E.'s of not less than 30 seconds each and 1 S.S.E.
of not less than 40 seconds.
In establishing the required input acceleration, the following considerations were given. The Sample Pump is panel mounted. Therefore, the required response motion for all directions is that shown in Figure E-1 for Generic Qualifi-cation. The test response spectra enveloped the required response spectra to the extent capable given limitations of the test table.
4,6.6.1 The Sample Pump was mounted on the shake table in a manner that dynamically simulates the recommended mounting.
A photograph showing mounting details 1s provxdecl ~
A control accelerometer was mounted adjacent to an input mounting point.
During the performance of the seismic tests the control accelerometers and response accelero-meters were recorded.
The control accelerometers output for the complex random tests was routed through a shock spectrum analyzer and the data was pre-sented as a peak response of frequency. One representative OBE and SSE TRS was plotted at 5% damping for a longitudinal/vertical and lateral/vertical test run. The location of each input and response accelerometer is identified on the plot of the shock response spectra.
4,6, The Sample Pump was energized (as applicable) during the performance of seismic tests. Output response (such as pressure, current, position, etc.) was monitored throughout the test.
4,6,1 Upon completion of the seismic vibration tests the Sample Pump was functionally tested and results were documented as described in para-graph 4..2 above. Performance data was compared with those that were previously obtained and any deviations were evaluated.
4.7 Simulated Post Accident Condition 4.7. The objective of this environmental exposure was to verify the capability of the equipment to operate under a postulated Design Basis Accident. The Simulated Post Accident Condition exposure consisted of exposure to radiation, pressure, temperature and humidity. The post accident exposure to radiation was combined with the expected in-service radiation exposure as described in paragraph 4.5 Irradiation.
- 4. 7. The Simulated Post Accident Condition exposure was performed in a controlled= environmental chamber. Appendix F lists the test variables (i.e., temperature, humidity, pressure) and time profile.
4.7. The Sample Pumps were periodically monitored during the performance of these tests. Upon completion, the K-IV Hydrogen Analyzer Sample Pumps were functionally tested and results were recorded as described in paragraph 4.2.
4.7. The Sample Pumps were mounted and connected in a manner that simulates their installation when in actual use.
4.7. 5 The Sample Pumps were operated continuously during the Post Accident exposure.
4.8 Failure Ana~ls i s 4.8.1 Xn the evaluation of the qualification test results, any sample equipment was assumed to have failed when the equipment did not perform Class 1F. functions required by the equipment specifications.
4.8.2 If a failure occurred during the qualification test process, this would not necessarily con-stitute a failure to qualify. It must be determined if the failure was random or an end-of-life failure. True random failures by definition do not impact qualified life.
4.8.3 If end-of-life or random failure was established as the cause of failure, a replacement plan was initiated for the component which failed if such replacement was feasible. If such re-placement was not feasible, the equipment was considered to have reached end-of-life.
4.8.4 If the appropriate component replacement plan
'/ Mm (
was to be implemented, the qualified life of 0 ~
~ ~
the equipment was not degraded.
- 4. 9 Acce 'tance Cr'iteria an'd Qua'la'fic'ation Report 4.9.1 To meet the provisions set forth by IFEE-323-1974, the qualification program was to be ac-companied by a detailed report documenting all tests, data, etc., and the acceptance criteria.
4.9.2 The acceptance criteria for Service Condition Simulation and Aging exposure was successful simulation of the design life. The Hydrogen Analyzer Sample Pump was required to perform after the simulated accelerated aging process without the loss of Class lE function and structural integrity,
- 4. 9.3 The acceptance criteria for Simulated Post Accident Conditions exposure required that loss of Class lE performance did not occur, and structural integrity was maintained.
4.9.4 The acceptance criteria for Seismic exposure required that structural integrity was main-tained, loss os Class lE performance did not occur during or after the excitation of one Safe Shutdown Earthquake and five Operation Basis Earthquakes.
4.9.5 A qualification report would be prepared and certified by a registered professional engineer.
The report contains all of the detailed test procedures, measurements, description of test instrumentation, fixtures, calibration data and interpretations, and data on, and explanation of any anomalies, The qualified life of. the
particular component instruments shall be delineated as the period of time for which satisfactory performance can be demonstrated for the specified set of service conditions.
5.0 Qualification Test Results
- 5. 1 ~Summar The environmental qualification type tests, described in Section 4.0 of this report were performed in sequence, as recommended by Std.
IEEE-323-1974. The 100 day Simulated Post Accident Condition environmental test concluded on 9/17/82, and the Functional Test and Final Inspection and Operational Tests were performed on 9/20/82. All five test items, Pump Nl through Pump /f5, were found to be completely functional and free of any degradation preventing the per-formance of their Class lE function.
44 RGGE Correspondence Concerning Limit Switches, March 3, 1978
'5.
Design Approval Test on Material Used in Westinghouse Penetrations for the Brunswick Station of Carolina Power and Light Company August ll, 1972
- 46. Test Data for Coleman and Rme Cable 4V'. Aging Failure Detection Program, May 6, 1980 Valcor Solenoid Valve: Vendor Data.
- 50. Westinghouse Terminal Blocks Qualification Superseded
- 51. Cable Identification and Qualification Supplement, Including F&5074 (Supplement) Concerning Coleman Silicone-Rubber-Insulated Cable Qualification
- 52. Wide-Range Sump Level Switch Specification Superseded. See 81.
- 53. Limitorque Valve Operator Data, Including Limitorque Report B0003 and Section 4.1.4 of B0058
- 54. Containment Electrical Penetration Analysis, RG&E Letter dated 4/12/79
- 55. Kerite Letter, June 26, 1980
- 57. Control Valve Specification SP-513-044666-000, September 27, 1974, Concerning Standby AFW Valves Mild
- 58. Westinghouse 10/10/80 Letter Concerning Crouse-Hinds Electrical Penetrations
- 59. Evaluation of Aging Effects on Organic Materials used in Crouse-Hinds Electrical Penetrations
- 60. Westinghouse Terminal Block Information on Aging and Radiation Superseded
- 61. Aging Evaluation of Westinghouse Electrical Penetrations
- 62. Raychem Splice Sleeve Aging Information
- 63. Kerite Cable Aging Information Containment Fan Cooler Motor Splices Safety-Related Motor Bearings Maintenance and Lubrication, including extracts from Ginna Maintenance Procedure A-1011
- 66. Deleted.
- 67. Safety-Related Motor Characteristics (Insulation)
- 69. Westinghouse Research Report 71-1C2-RADMC-Rl, December 31, 1970 (Revised April 10, 1971), Concerning "The Effect of Radiation on Insulating Materials Used in Westinghouse Medium Motors" extracts
- 70. WCAP-7829, "Fan Cooler Motor Unit Test"
- 71. WCAP-7706-L, An Evaluation of Solid State Logic in Reactor Penetration in Anticipated Transients
- 72. Maintenance/Surveillance for Aging Program at Ginna
- 73. Valcor Report QR 52600-5540-2
- 74. LVDZ
- 75. Namco Limit Switch
- 76. EPRI Report 1707-3
- 78. Kerite Cable Report for Ginna Proprietary
- 79. Conax RTD Test Report Sumnary
- 80. Chevron NRRG Grease and Portions of A-1011
- 81. TransAmerica (GEM) DeLaval Sump B Level, including connecting BIW cable
- 82. Post-accident sampling system, SOV 955.
- 84. Mobil Oil radiation data.
t I'lp S
I F D
RGGE Reference 84 I Mobil Oil Corporation 670 WHITE PLAINS ROAD SCARSDALE. NEW YORK 10583 February 2, 1984 Mr. George Wrobel Rochester Gas 5 Electric 49 East Avenue Rochester, New York 14649
Dear Mr. Wrobel:
This confirms the information given to you on the radiation tolerances for specific Mobil products.
Maximum Mobil Product Rad Levels Mobil DTE 25 3 x 108 Mobil DTE 26 3 x 108 Mobilux EPl 3 x 108 Mobilux EP2 3x 108 The values quoted for Mobil DTE 25, 26 are the radiation effects based on an 18K change in their viscosities. Values for Mobilux EP1 and EP2 are based on a 15-20K change in penetration. For your further information, our Gamma irridation studies were carried out in a 5MW reactor under static conditions immediately after reactor shutdown. Typical dosage rate varied between 2 x 10 rad/hour to
~
2 x 10 rad/hour.
Please advise if we can be of any assistance.
Very truly yours, DM:lac D. Magana 2099L/3 Chief Engineer Northeast Commer'cial Division CC: D.C. Stanek
- 3. M.
L.W.
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GINNA STATION (DOCUMENTATION REFERENCE)
- l. Crouse-Hinds Penetration Test Report
- 2. Gilbert Spec. 520 Standby AFW Pumps Mild 3~ Gilbert Spec. 711 Standby AFW Pumps Motors Mild 4~ Gilbert Spec. 5201 Large Motors
- 5. Deleted. Included in Reference 51
- 6. Gilbert Spec. 5342 HVAC Throughout Ginna Mild
- 7. Gilbert Spec. RO-2239 Diesel Generators Mild
- 8. Gilbert Spec. RO-2267 Auxiliary Feedwater Pumps Mild
- 9. Gilbert Spec. R0-2400 Batteries Mild
- 10. IPCEA Std. S-61-402, Sect. 3.8 and 4.3.1 PVC Cable
- 11. Kerite Cable Memo 7/22/68
- 12. NEMA Std. SG-3, Low Voltage Circuit Breakers Mild
- 13. Westinghouse Spec. 676258 Motor Operated Valves
- 14. Westinghouse Spec. 676270 Control Valves
- 15. Westinghouse Spec. 676370 Auxiliary Pumps
- 16. Westinghouse Spec. 676427 Auxiliary Pump Motors
- 17. WCAP 7343, Irradiation Testing of Reactor Containment Fan Cooler Motor Insulation, June, 1969
- 18. WCAP 7410-L, Environmental Testing of Engineered Safety Features Related Equipment, Vol. I & II, 12/70
Vol. I & II, 12/70
- 20. WCAP 9003, Fan Cooler Motor Unit Test, January, 1969
- 21. Deleted. Included in Reference 45 22, Westinghouse Terminal Blocks Superseded Report NSME-775, Fail-Safe Operation of ASCO Solenoids Superseded Copes-Vulcan Solenoid Valves Superseded
- 25. Vendor Data on Laurence Solenoid Superseded
- 26. Vendor Data on Versa Solenoid Superseded
- 27. WCAP 7153, Investigation of'Chemical Additives for Reactor Containment Sprays
- 28. Deleted. Included in Reference 45
- 29. Gilbert Spec. 504 Westinghouse Electrical Penetrations
- 30. Technical Proposal for Electric Penetration for Ginna Containment Structure by Westinghouse September 4, 1974
- 31. WCAP 7354-L, Supplier Post Accident Testing of Process Instrumentation
- 32. Vendor Data on Gould Batteries Mild
- 33. ,Westinghouse Spec. Sheets for Foxboro Transmitters Superseded
- 34. Vendor Data on Barton 289 Transmitter Superseded
- 35. Rosemont RTD Spec. Superseded
- 36. Vendor Data on Raychem Splice Sleeves
- 37. June 16, 1975 Letter to R. A. Purple from L. D. White on Containment Flooding
- 38. April 4, 1979 FRC Final Report FW5074, Raychem Splice Sleeves and Kerite Cable 39-
- 42. Deleted.
- 43. Design Criteria Standby Aux. Feedwater System October 24, 1974 Mild Note 1: "Mild" environment equipment is defined in 10 CFR 50.49.
Note 2: References designated as "superseded" are for items which have been replaced by other environmentally qualified equipment.
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